| MT | Reaction | 0.0253-eV | Maxwellian Average |
g-factor | Resonance Integral |
14-MeV | Fiss. Spec. Average |
|---|---|---|---|---|---|---|---|
| 1 | (n,total) | 2.217 (kb) | 2.201 (kb) | 0.993 | − | 5.239 (b) | 6.662 (b) |
| 2 | (n,elastic) | 66.70 (b) | 74.09 (b) | 1.111 | − | 2.762 (b) | 4.607 (b) |
| 4 | (n,inelastic) | ( E-thr = 159.2 keV ) | 280.7 (mb) | 2.017 (b) | |||
| 16 | (n,2n) | ( E-thr = 6.682 MeV ) | 2.189 (b) | 8.832 (mb) | |||
| 17 | (n,3n) | ( E-thr = 15.03 MeV ) | − | 3.166 (μb) | |||
| 22 | (n,na) | 0.000 (b) | 0.000 (b) | − | 2.730 (nb) | 6.475 (μb) | 2.747 (nb) |
| 28 | (n,np) | ( E-thr = 7.276 MeV ) | 16.21 (μb) | 17.09 (nb) | |||
| 102 | (n,γ) | 2.150 (kb) | 2.127 (kb) | 0.989 | 438.7 (b) | 196.3 (nb) | 29.61 (mb) |
| 103 | (n,p) | 0.000 (b) | 0.000 (b) | − | 43.50 (μb) | 3.584 (mb) | 2.543 (μb) |
| 104 | (n,d) | ( E-thr = 5.040 MeV ) | 272.9 (μb) | 78.64 (nb) | |||
| 107 | (n,a) | 0.000 (b) | 0.000 (b) | − | 9.934 (μb) | 471.9 (μb) | 569.5 (nb) |
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These cross sections are calculated from JENDL-4.0 at 300K.
The background color of each cell noted a cross section means the order of the cross-section value.
The unit of cross section, (b), means barns, and SI prefixes are used as following.
(kb) → 103(b), (mb) → 10−3(b),
(μb) → 10−6(b), (nb) → 10−9(b).
MT is a number that defines a reaction type. For the relation between MT and reaction type, please see here or refer to the manual of ENDF formats.
Maxwellian Average :
where T denotes the temperature, and kB the Boltzmann constant.
The upper and lower limits of integration, EL and EU
are set to 10−5 eV and 10 eV, respectively.
Resonance Integral :
with EL = 0.5 eV and EU = 10 MeV.
U-235 Thermal Fission-Neutron Spectrum Average (Fiss. Spec. Average) :
with EL = 10−5 eV and EU = 20 MeV.
The parameters a and b are 0.988 MeV and 2.249 MeV−1, respectively.
Westcott g-factor :
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